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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ENS 41331 +
- ML19282D029 +
- ML19284A711 +
- ML20063G129 +
- ML022330062 +
- ML20087M659 +
- ML20077A014 +
- ML20100B056 +
- ML20093F444 +
- ML20138M754 +
- ML20069A274 +
- ML20195D000 +
- DCL-21-017, DC-2021-01 Post Exam Comments Analysis +
- GO2-84-426, Responds to NRC Re Violations Noted in IE Insp Rept 50-397/84-09.Corrective Actions:Air Lock Door Relocked, Air Lock Repaired & Plant Removed from Tech Spec Action Statement 3.6.1.3.9.1 +
- 05000414/LER-1989-015, :on 890609,operating Main Feedwater Pump Tripped on Low Suction Pressure Initiating Auxiliary Feedwater Pump Automatic Start & Turbine Trip.Caused by Equipment Malfunction +
- 05000249/LER-1986-008-08, :on 860618,Group II Primary Containment Isolation Received,Causing Isolation of Reactor Bldg Ventilation & Start of Standby Gas Treatment Sys.Caused by Personnel Error.Personnel Cautioned Re Maint +
- 05000382/LER-1987-028, :on 871211,reactor Trip Occurred Due to Inadvertent Shutting of Msiv.Caused by Solenoid Valve Stuck Open During Testing.Solenoid Valve Replaced & MSIV Tested Successfully Prior to Restarting of Plant +
- 05000325/LER-1988-017, :on 880630,HPCI Sys Declared Inoperable Due to Inoperability of Steam Line Flow Instrument.Also on 880701, Hcpi Turbine Steam Supply Isolation Would Not Open.Caused by Failure of Valve Motor Windings +
- 05000280/LER-1985-010, :on 850515,intermediate Range High Flux Trip Bistables NI-35 & NI-36 Tripped at 30% & 31% Power, Respectively.Apparently Caused by Lack of Experience in Developing Intermediate Setpoints +
- 05000461/LER-1995-005, :on 950515,RRPs Tripped from Fast to Slow Speed Due to Fault in Reactor Recirculation Control Panel +/- 15 Volt Dc Field Bus Bars.Nest Assembly Which Contained Faulty Field Bus Bars Replaced W/Spare Nest Assembly +
- 05000416/LER-1993-010-02, :on 931004,automatic Closure of GGNS Residual Heat Removal Sys Containment Isolation Valve 1E1F008 Occurred While RHR B in Shutdown Mode.Caused by Failure in Battery Charger.Faulty Limiting Card Replaced +
- 05000416/LER-1993-010, :on 931004,loss of Shutdown Cooling & ESF Actuation Occurred During Unit Outage Due to Class 1E Bus Voltage Oscillations.Replaced Faulty Current Limiting Card +
- ML20045B336 +
- 05000461/LER-1990-012, :on 900517,feedwater Sys Flow Channel Failed & Caused Sensed Low Feedwater Flow.Caused by Normal end-of- Life Failure for Converter.Power Converter Replaced & Preventive Maint Tasks Established +
- ML20010B479 +
- 05000272/LER-1987-012-02, :on 870930,Tech Spec 3.0.3 Entered Since Inoperable Undervoltage Trip Channel Not Placed in Tripped Condition within 1 H.Caused by Inadequate Relay Dept Procedures.Manual to Be Revised +
- 05000272/LER-1987-012-01, :on 870930,Tech Spec 3.3.1.1 Action 6 Entered When Preventive Maint Performed on Group 1G Bus Reactor Coolant Pump Undervoltage Trip Relay.Caused by Inadequate Procedures.Relay Dept Manual Revised +
- 05000397/LER-1991-027, :on 910930,question on Jet Operability & Surveillance Applicability in Operational Conditions 1 & 2 Below 25% Rated Thermal Power Raised.Caused by Inadequate Procedure.Ts Amend Request Will Be Submitted +
- 05000397/LER-1991-028, :on on 910930,containment Airlock Door Seal Leakage Test Not Performed within Allowable Surveillance Interval.Caused by Inadequate Personnel Work Practices. Master Startup Checklist Amended +
- 05000259/LER-2011-006, For Browns Ferry, Unit 1, Regarding Loss of Safety Function (HPCI) Due to Primary Containment Isolation +
- 05000296/LER-2011-001, For Browns Ferry Nuclear Plant, Unit 3, Regarding Loss to Shutdown Cooling (RHR) +
- 05000259/LER-2011-003, For Browns Ferry, Unit 1, Regarding Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip +
- 05000259/LER-2011-001, For Browns Ferry Nuclear Plant, Unit 1, Regarding Three-Unit Scram Caused by Loss of All 500-kV Offsite Power Sources +
- 05000259/LER-2011-005, Regarding Reactor Water Level Scram Due to Distracted Operations Crew +
- ML17334B395 +
- ML17305A580 +
- ML21075A088 +
- 05000325/LER-1988-018, :on 880713,testing Revealed That HPCI Pump Suction Primary Containment Inboard Isolation Valve Would Not Open.Caused by Loss of Electrical Continuity in Opening Logic.Valve Geared Limit Panel Replaced +
- 05000341/LER-1995-006, :on 950602,main Turbine Trip Occurred Due to False Overspeed During Mechanical Overspeed Test.Revised Procedure 27.112.01 to Incorporate Holding Overspeed Reset Pushbutton Depressed at Least 15 Seconds +
- 05000311/LER-1983-066-03, /03L-0:on 831220,common Suction Valve 2RH1 Closed, Resulting in Loss of RHR Flow.Caused by Personnel Error.Rhr Pump 22 Started & RHR Flow Reestablished within 22 Minutes +